Generate QR code
Open Access
Subscription Access
Estimation of hydrides structure and mechanical properties of irradiated E110 alloy after thermomechanical tests imitating dry storage conditions
https://doi.org/10.22349/1994-6716-2024-119-3-210-220
Abstract
Safety assurance of spent nuclear fuel dry storage requires reliable prediction of mechanical properties of fuel element cladding depending on structural changes at all stages of nuclear fuel handling. In this work investigations of hydrides structure in irradiated fuel element cladding made of E110 alloy have been conducted in irradiated state as well as after tests simulating dry storage conditions. Using the program code, the coefficients that best correlate with mechanical properties have been found.
Keywords
fuel element cladding,
zirconium alloys,
E110,
zirconium hydrides,
mechanical properties,
dry storage
Supporting agencies: The work was performed under the order of JSC TVEL using the experimental base of the research complex of material science protective chambers of NRC “Kurchatov Institute”.
About the Authors
O. O. Zabusov
National Research Center “Kurchatov Institute”; National Research Nuclear University “MEPhI”
Russian Federation
Russian Federation
Cand Sc. (Phys-math)
1 Kurchatov Sq, 123182 Moscow
31 Kashirskoe Hw, 115409 Moscow
A. V. Ugryumov
Joint-Stock Company “TVEL”
Russian Federation
Russian Federation
Cand Sc. (Eng)
49 Kashirskoe Hw, 115409 Moscow
M. M. Grekhov
Joint-Stock Company “TVEL”
Russian Federation
Russian Federation
Cand Sc. (Phys-math)
49 Kashirskoe Hw, 115409 Moscow
D. A. Maltsev
National Research Center “Kurchatov Institute”
Russian Federation
Russian Federation
Cand Sc. (Eng)
1 Kurchatov Sq, 123182 Moscow
A. A. Shishkin
Joint-Stock Company “TVEL”
Russian Federation
Russian Federation
49 Kashirskoe Hw, 115409 Moscow
R. A. Kurskiy
National Research Center “Kurchatov Institute”
Russian Federation
Russian Federation
1 Kurchatov Sq, 123182 Moscow
A. V. Rozhkov
National Research Center “Kurchatov Institute”
Russian Federation
Russian Federation
1 Kurchatov Sq, 123182 Moscow
References
1. Kalinkin, V.I., Anisimov, O.P., Razmashkin, N.V., Tikhonov, N.S., Simanovsky, V.M., Khranenie OYaT – obyazatelnoe uslovie razvitiya atomnoi energetiki [Spent nuclear fuel storage as a necessary condition of nuclear energy development], PRoAtom, 2006. URL: http://www.proatom.ru/modules.php?file=article&name=News&sid=770 (reference date 15/01/2024).
2. Kalinkin, V.I., Kritsky, V.G., Tokarenko, A.I., Tikhonov, N.S., Razmashkin, N.V., Serova, A.L., Storage of spent nuclear fuel of commercial reactors [Khranenie otrabotavshego yadernogo topliva energeticheskikh reaktorov], St Petersburg: VNIPIET, 2009.
3. Ruiz-Hervias J., Simbruner K., Cristobal-Beneyto M., Perez-Gallego D., Zencker U. Failure mechanisms in unirradiated ZIRLO® cladding with radial hydrides, J. Nucl. Mater., 2021,V. 544, Art. 152668.
4. Konarski, P., Cozzo, C., Khvostov, G., Ferroukhi, H., Spent nuclear fuel in dry storage conditions – current trends in fuel performance modeling, J. Nucl. Mater., 2021, V. 555, Art. 153138.
5. Simon, P.C.A., Frank, C., Chen, L.Q., Daymond, M.R., Tonks, M.R., Motta, A.T., Quantifying the effect of hydride microstructure on zirconium alloys embrittlement using image analysis, J. Nucl. Mater., 2021, V. 547, Art. 152817.
6. Kobylyansky, G., Mazaev, A., Zvir, E., Eremin, S., Chertopyatov, E., Obukhov, A., The effect of long-term annealing simulating the parameters of dry storage of VVER-1000 fuel rods on the mechanical properties of E110 alloy shells in the longitudinal direction [Vliyanie dlitelnogo otzhiga, modeliruyushchego parametry sukhogo khraneniya tvelov VVER-1000, na mekhanicheskie svoistva obolochek iz splava E110 v prodolnom napravlenii], Phys. Chem. Mater. Treat., 2021, No 4, pp. 42–49.
7. Motta, A.T., Capolungo, L., Chen, L.Q., Cinbiz, M.N., Daymond, M.R., Koss, D.A., Lacroix, E., Pastore, G., Simon, P.C.A., Tonks, M.R., Wirth, B.D., Zikry, M.A., Hydrogen in zirconium alloys: a review, J. Nucl. Mater., 2019, V. 518, pp. 440–460.
8. Kursky, R.A., Safonov, D.V., Zabusov, O.O., Frolov, A.S., Maltsev, D.A., Rozhkov, A.V., Shishkin, A.A., Evolyutsiya struktury gidridov v obluchennom splave E110 pri termomekhanicheskikh ispytaniyakh, imitiruyushchikh zakriticheskie (predelnye) rezhimy sukhogo khraneniya [Evolution of the hydride structure in irradiated E110 alloy in the process of thermomechanical treatment simulating supercritical dry storage conditions], Izvestiya vuzov. Yadernaya Energetika, 2023, No 1, pp. 108–120
9. Kursky, R.A., Rozhkov, A.V., Zabusov, O.O., Maltsev, D.A., Skundin, M.A., Bandura, A.P., Vasilieva, E.A., Shishkin, A.A., Vliyanie termomekhanicheskogo vozdeistviya na strukturu gidridov v obluchennykh obolochechnykh trubakh iz splava E110 v usloviyakh dlitelnogo sukhogo khraneniya otrabotavshego yadernogo topliva [Influence of thermomechanical exposure on the structure of hydrides in irradiated E110 alloy cladding pipes under the conditions of long-term dry storage of spent nuclear fuel], Voprosy Materialovedeniya, 2022, V. 1 (109), pp. 199–214.
Review
For citations:
Zabusov O.O., Ugryumov A.V., Grekhov M.M., Maltsev D.A., Shishkin A.A., Kurskiy R.A., Rozhkov A.V. Estimation of hydrides structure and mechanical properties of irradiated E110 alloy after thermomechanical tests imitating dry storage conditions. Voprosy Materialovedeniya. 2024;(3(119)):210-220. (In Russ.) https://doi.org/10.22349/1994-6716-2024-119-3-210-220
Views:
86
Email this article 